ML20006F454

Proposed Tech Specs Correcting Various Typos

ML20006F454
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	02/16/1990
From:	PORTLAND GENERAL ELECTRIC CO.
To:
Shared Package
ML20006F286	List: ML20006F285 ML20006F454 ML20006F459
References
NUDOCS 9002280048
Download: ML20006F454 (23)

Text

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LCA 192 e

Attachment B Page 1 of~23 o

1,0 DEFINITIONS l

'I IDEFINEDTERMS

((The DEFINED TERMS of this section appear in capitalized type and are applicable throughout these Technical Specifications.

THERMAL POWER 1.3l

%2-THERMAL POWER shall be total reactor core heat transfer rate 4

to the reactor coolant.

RATED THERMAL POWER I.z4 M

i dt RATED THERMAL POWER shall be r, total reactor core heat transfer rate to the reactor coolant of 3411 mit.

OPERATIONAL MODE OR MODE I 10.

l. # 8 I

l 1 + An'0PERATIONAL MODE shall correspond to any one inclusive combination of core reactivity. condition, power level and average reactor coolant

' torperature specif.ied in Table 1.1.

1 ET1M

l. I 1.5 ACTION shall be those additional requirements specified as corollary statements to each principal specification and shall be part of the specifications.

'(

OPERABLE - OPERABILITY 3.17 3 -1* A system, subsystem, train, component or device shall be OPERABLE or have OPERA 81LITY when it is capable of performing its specified safety-related function (s). Implicit in this definition shall be the l.10.

-c assumption that all necessary attendant instrumentation, controls, normal L

and' emergency electric power sourceis, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train,

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component or device to perforsa its safety-related function (s) are also l/10%

capable of performing their rated support function (s).

I Nonessential portions of a system, subsystem, train, component, or device need not be operational as long as its lack of' operational capability does not in any way degrade the safety-related function (s) of the system, sub-system, train, component, or device. For example, the Component Cooling Water System need not be declared inoperable if the waste gas compressor af tercooler is isolated due to a leak in the af tercooler since*this

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portion of the systes does not perform a safety-related function. As a (L%. i

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further example, consider a failure of the manual operator on valve 8921A

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(SI Pump A discharge isolation) such that the valve cannot be repositioned. f

/l If the valve is open, there is no safety-related impact since this does I

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not prevent the SI-train from performing its safety-related function.-

(

However, if the valve is shut, then the SI Train A would be declared

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inoperable since it cannot perform its safety-related function.

L TRO.1AN-UNIT 1 1-1 AmendmentNo.J3.l4I g

{rebruary10, 165b, 9002280048 900216 PDR ADOCK 05000344' P

PNV

LCA 192.

Attachment B

• f Page 2 of 23 DEFINITIONS T

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REPORTA8LE EVENT

1. ze f

Ir7-A REPORTABLE EVENT shall be any of those conditions specified in

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s Section 50.73 of 10 CFR Part 50.

CONTAINMENT INTEGRITY f. to J

ht CONTAINMENT INTEGRITY shall exist when:

1.8.1 All penetrations required to be closed _ during accident conditions are either:

a.

Capable of being closed by an OPERABLE containment automatic isolation valve system, or b.

Closed by manual valves, blind flanges, or. deactivated automatic valves secured 4 their closed positions, except L

as provided in Table 3.6-1 of Specification 3.6.3.1 I

1.8.2 All equipment hatches are closed and sealed.

1.8.3 Each air lock is OPERA 8LE pursuant to Specification 3.6.1.3, and p

1.8.4 The containment leakage' rates are within the limits of Specification 3.6.1.2.

_CFANNEL CALIBRATION 83 a

tit-A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that,it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.-

The CHANNEL CALIBRATION may be performed by any series of sequential, over-lapping or total-channel steps such that the entire channel is calibrated.

CHANNEL'CHECX t. *f -

d

-M O-A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This detemination shall include, f-where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

TROJAN - UNIT 1 1-2 Amendment No. 27, 97, M J

kombii~2071M43

a LCA 192 Attachment B Page 3 of 23 l-1; L

DEFINITIONS J-L CHANNEL FUNCTIONAL TEST i, !T j

-Tr14-A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

CORE ALTERATION I, 6 p

- 1r12-CORE ALTERATION shall be the movement or manipulation of any component within the reactor pressure vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe conservative position.

SHUTDOWN MARGIN 1.27 j9r13-- SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by 1

p which the reactor is or would be suberitical from its present condition l 97 assuming all fuil lenth rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.

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IDENTIFIED LEAKAGE-1.14 IDENTIFIED LEAKAGE shall be:

a.-

. Leakage (except CONTROLLED LEAKAGE) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or L

b.

Leakage into the containment atmosphere from sources that are L

both specifically located and known either not to interfere L

with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or c.

Reactor coolant system leakage through a. steam generator to the secondary system.

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UNIDENTIFIED LEAKAGE l

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7 1.15-UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LSAKAGE or CONTROLLED LEAKAGE.

TROJAN-UNIT 1 1-3 p ) mendment No. 79, pf D.Y. _30y_ g 3

--h LCA 192J Attachment B.

-Page 4 of 23'

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OgTINITTONS PRESSURE SOUNCARY 4.ptAGE I,40

-1d6--PRES 3URE SOUNDARY LENAEE shall be leakage {axtept steam generator tube leakage) through a non-isolable fault in a Reactor Coolant System camponent body pipe wall or vessel wall.

CONTROLLED LDKAtt 1,7 L

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-id7-. C0K!1 TOLLED LEAXAGE shall be that seal water flow from the reactor castaat pump seals.

QUADRANT 90W S TTLT RATIO

1. ,2 3

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- -id6-QUADRANT POWER TILT RATIO shall ba the ratio of the maxiasa upper sacort detector calibrated output to the average of the upper encore detector calibrated outputs, or the ratio of the maximum lower ancore detector calibrated output to the. average of the lower extors detector calibrated outputs, whichever is greatar. With one encore detector inoperable. the remaining three detectors shall be used for computing the average.

DOSE EDUfvALENT t-131

p. 9 d-4AS-- 00$t EQUIVALENT I-131 shall be that concentration of I-131 (uct/ gram) y which alone would produca the same thyroid dose ~as the quantity and isotopic srixture of I-131. I-132.1-133.1-134. and I-135 actually present.

The thyroid dose convarsion factors used for this calculation shall be those listed in Table III of TID-14844 ' Calculation of 01stanca Factors for Power and Test Raactor Sitas".

STA68D ED TEST 8Asts 4 30 A te'A STASSERED TEIT BASIS shall consist of:

a.

A test schedule for n systems, subsystans, trains or other designated components ottained by dividing the specified test interval into n equal subintarvals, b.

The tasting of one systas, subsystes, train or other designated component at the beginning of each subintarval.

FRECUENCY NOTATICM 4./ 2.

2_hp. The FREQJDtCT NOTATION specified for the performanes of Surve111anco Requirements shall correspond to the intarvals defined in Table 1.2.

TROJAN-UNIT 1 14 1

Attachment'B Page 5 of 23 J

4 DEFINITIONS REACTOR TRIP SYSTEM RESPONSE TIME I. zr

.9-hts The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its. trip setpoint at the channel sensor until loss of stationary gripper coil voltage.

ENGINECRED SAFETY FEATURE RESPONSE TIME f.1/

j 4223-The ENGINEERED SAFETY FEATURE RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation i

setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel-to their re -

quired positions, punp' discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where appitcable.

AXIAL FLUX DIFFERENCE t. z.

4 Mt& AXIAL FLUX DIFFERENCE shall be the difference in nonnalized flux signals between the top and bottom halves of. a two section excore neutron -

detector.

PHYSICS TE E

1. I'l

-21.25-PHYSICS TESTS shall be those tests perfonned to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 14.0 of the FSAR, 2) authorized under the provisions of 10 CFR'50.59, or 3) otherwise approved by the Commission, f - AVERAGE DISINTEGRATION ENERGY 1.10 f-1M T shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the-sum of the average beta and ganna energies per disintegration (in MeV) for isotopes other than iodines,- with half lives greater than 15 minutes,

making up at least 95% of the total non-iodine activity in the coolant.

k TROJAN-UNIT 1 1-5

LCA 192' I

Attachment B Page 6 of 23 3

1.0 DEFINITIONS (Continued) i SOURCE CHECK

'q * '

I 2'l

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- IM A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to either an installed detector check source or to a background radiation level if background exceeds the insta11edk check source strength.

PROCESS CONTROL PROGRAM

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J 1,38 A PROCESS CONTROL PROGRAM (PCP) shall be the manual or set of operating; procedures detailing the program within which SOLIDIFICATION of radioactive wastes from liquid systems is assured. Requirements of the PCP are provided in Specification 6.14 l

SOLIDIFICATION

/.z o j5 1,29. SOLIDIFICATION shall be the conversion of radioactive wastes from i

liquid systems to a form that meets shipping and burial ground requirenents.

0FFSITE DOSE CALCULATION MANUAL-(0DCM) r.t 9 A

j 14 An 0DSITE DOSE CALCULATION MANUAL (ODCM) shall be a manual containing

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the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alann/ trip set-points. - Requirements of the 00CM are provided in Specification 6.15.

GASEQUS RADWASTE TREATMENT SYSTEM

l. 3

- 1J1-The GASEOUS RADWASTE TREATMENT SYSTEM is the system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment..

VENTILATION EXHAUST TREATMENT SYSTEM b Ss j

W VENTILATION EXHAUST TREATMENT SYSTEMS are those systems designed and installed to reduce gaseous radioiodine or radicactive material in partic-ulate fonn in effluents by passing the ventilation exhaust from the Fuel' and Auxiliary Buildings and the Containment purge through HEPA filters prior to the release to the environment. Such systems are not considered to have any effect on noble gas effluents.

k TROJAN-UNIT 1 1-Sa

, AmendmentJo. N

(' December 20,1984)

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LCA 192 -

Attachment B-o Page 7 of 23 l'.D - DEFINITIONS (Continued)

PURGE - PURGING

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--4.34-PURGE or PURGING is the process of discharging air from the Con-tainment utilizing the Containment Purge Supply and Purge Exhaust

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LIQUID RADNASTE TREATENT SYSTEM MN The LIQUID RADNASTE TREATENT SYSTEM is the system used to mduce L

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radioactive materials in liquid effluents by filtering, dominera11 zing,

-and providing holdup or decay of the radioactive wastes for the purpose of reducing-the total radioactivity prior to release to the environment.

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TROJAN-UNIT 1 1-Sb Amendment No,49' 20,198}4]

ecember t

LCA 192-I Attachment B-Page 8 of-23 1

REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION ACTION 4 - POWER OPERATION may continue provided that within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either:

1.

The rod is restored to OPERABLE status within the above alignment requirements, or 2.

The rod is declared inoperable and the SHUTOOWN MARGIN requirement of Specification 3.1.1.1 is satisfied.

POWER OPERATION may then continue provided that:

4 a) An analysis of the potential' ejected rod worth is performed within 3 days and the rod worth is deter-mined to be 5 0.98% ak at zero power and 5 0.21%

Ak at RATED THERMAL POWER for the remainder of the fuel cycle, and b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and c) The THERMAL POWER level is reduced to < 75% of RATED THERMAL POWERCjliiiDCone hour and within the next goliffThe high neutron flux trip setpoint is reduced p,

to < 85% of RATED THERMAL POWER, or' lo w e/'

d) The remainder of the rods in the group with the

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cds(L inoperable rod are aligned to within i 12 steps of the inoperable rod within one hour while maintaining the rod sequence and insertion limits of Figures 3.1-1 and 3.1-2; the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.5 during subsequent operation.

-SURVEILLANCE REOUTREMENTS 4.1. 3.1.1 The position of each rod shall be determined to be within the l

group demand limit by verifying the individual rod positions at least once L

per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

s movement of at least 10 steps in any one direction at least once per 31-day 4.1. 3.1. 2 Each rod not fully inserted shall be determined to be OPERABLE b TROJAN-UNIT 1 3/4 1-19 Amendment _No.70,///

l l-1 Q 59~29, 19 {

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LCA 192-Attachment B Page 9 of 23 l

l-j POWER DISTRIBUTION LIMITS ACTION: '(Continued)'

c.

Identify and correct the cause of-the out-of-limit condition prior-to increasing THERMAL POWER above the reduced THERMAL POWER limit required by ACTION items a.2 and/or b above;

. subsequent POWER OPERATION may proceed provided that the combination of(RMd indicated RCS total flow rate are gdemoriitrited?through incore flux mapping and RCS total' flow w t-rate comparison. to be within the region of acceptable' opera '

tion shown on Figure 3.2-3 or 3.2-4 (as applicable) prior to 1

Ig exceeding the following THERMAL POWER levels:

+

1.

A nominal 50% of RATED THERMAL POWER, 2.

A nominal-75% of RATED THERMAL POWER, and 3.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of attaining > 95% of RATED THERMAL POWER.

e SURVEIL 8.ANCE RE0VIREMENTS 4.2.3.1 The provisions of Specification-4.0.4 are not applicable.

4.2.3.2 The' combination of indicated RCS total flow rate and F shall bedeterwinedtobewithintheregionofacceptableoperationof j

Figure 3.2-3 and 3.2-4 (as applicable):

o a.

Prior to operation above 75% of RATED THERMAL POWER af ter each

=

fuel loading, and b.

At least once per 31 Effective Full Power Days.

Where:-

N-R " 1.56 {1.0 +

3 (1.0 - P)}, and N

N

-FAH = Measured values of F obtained by using the movable 9

incore detectors to 80tagn a power distribution map.

The measured values of F shall be used to calculate F sinceFigures3.2-3a$$3.2-4includemeasurement c$1culational uncertainties of 3.5% for flow and N

4% for incore measurement of F3g.

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4.2.3.3 The RCS total flow rate indicators shall be subjected to a CHANNEL CALIBRATION at least once per 18 months.

I' 4.2.3.4 The RCS total flow rate shall be determined by measurement at least once per 18 months.

TROJAN-UNIT 1 3/4 2-9 AmendmentJLo. #B, 76, /47 m

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[mMay24,1989D.-

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LCA 1921 Attachment B Page'10 of 23 POWER DISTRIBUTION LIMITS DNB PARAMETERS j

LIMITING CONDITION FOR OPERATION-3.2.5 The following DNB relat the limits shown on Table 3.

~ rameters shall be maintained within T

Reactor Coolant System Tavg l'

kqR *A 3J d I

a..

b.

Pressurizer Pressure

.c.

Reactor Coolant System Total Flow Rate APPLICABILITY: MODE 1

- r-ACTION:

With any of the above parameters exceeding its limit, restore the parameter to within it limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 5% of RATED 1HERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILLANCE REOUIREMENTS 4.2.5 Each of the parameters of Table 3.2-1 shall be verified to be within their limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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TROJAN-UNIT 1 3/4 2-12 Amendment.. Nom i:

' July 25, 1980 c

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.LCA 192 1

' Attachment B Page 11 of 23

/ Ql TABLE 3.3 12.

F!

(Continued)

)

TABLE NOTATION

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ACTION 23 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:

1.

At least two independent samples are analyzed in accordance with Table 4.11-1, and; 2.

At least two technically qualified members of the Facility i j

Staff independently verify the release rate calculations and discharge valving, and;-

y 3.

Initiate corrective action to return the channels to OPERABLE status; or Otherwise suspend release of radioactive effluents via this I

pathway.

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ACTION 24 With the number of channels OPERABLE-less than required by Mi L

the Minimum Channels OPERABLE requirement, effluent releases

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via' this pathway may continue provided grab samples. are l

analyzed for gross radioacti of detection of at least 10 yity (beta or gansna) at a limit

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l uC1/ gram; V

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At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when release is discharged into

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the Columbia River..

ACTION 25 With the nun 6e f channels OPERABLE less than required by i

the Minimum Channels OPERABLE requirements, collect and analyze-

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grab samples for gross radioactivity (beta or gansna) at a lower-limit of detection of at least 10-' uC1/M1 as defined in

. Table 4.11-1; 3

1.

At least once per 7 days when CCWS radioactivity is less

(

than-10-5 uti/mi and no indication-of leakage from the radioactive systems to the CCWS is observed.

n 2.

Othenvise, at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.-

i ACTION 26 With the number of channels OPERABLE less than required by the l

Minimum Channels OPERABLE requirement, effluent releases via.

this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.

3/4 3-57 j ( A ndment_No. M TROJAN-UNIT 1 December 20, 198 D

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-LCA 192 Attachment B

f.. _

Page 12 of 23 INSTRUMENTATION RADIOACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION I

LIMITING COND: TION FOR OPERATION t

3.3.3.11 The radioactive gaseous process and effluent monitoring instrumen-tation channels shown in Table 3.3-13 shall be OPERABLE with their alarm /

notexceededandtocomplywiththerequirementsofSpecifications3.3.27{

trip setpoints set to ensure that the limits of Specification 3.11.2.1 are 3.4.6.1 and 3.9.9. as applicable.

APPLICABILITY: As shown in Table 3.3-13.

ACTION:

i a.

With a radioactive gaseous process or effluent monitoring instrumentation channel alarm / trip setpoint less conservative than the value shown in Table 3.3-13, adjust the setpoint to

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within the limit without delay'or declare the channel in-

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operable.

b.

With less than the minimum number of radioactive gaseous process or effluent monitoring instrumentation channels OPERABLE.~take the ACTION shown in Table 3.3-13.

With the

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inoperable-instrumentation channels identified in Table 3.3-13 items ~1, 2, 3c, 4 and 5 not returned to OPERABLE status within i

o 30 days,- identify the cause of the inoperable channels in the Semiannual Radiological Environmental Report in lieu of any 4

other report, c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

3 SURVEILLANCE REQUIREMENTS h:

4.3.3.11.1 The setpoints shall be detemined in accordance with procedures f i

as described in the 00CM and shall be recorded.

1 4.3.3.11.2 Each radioactive gaseous process or effluent monitoring j

instrumentation channel shall be demonstrated OPERABLE by perfomance s

of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL l

FUNCTIONAL TEST operation at the frequencies shown in Table 4.3-9.

I TROJAN - UNIT 1 3/4 3-59 AmendmentNo./((

A CDEembh 5.~1984]

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l TABLE d.4 I I

g PRIMARY COOLANT SPECIFIC ACTIVITY SA!4PLE-o

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AND ANALYSIS PROGRAM

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TYPE OF MEASUREMENT HillIlOJI4 -

H0 DES IN WHICH A!!D ANALYSIS FREQUEllCY_

SURVEILLANCE REQUIRED 1.

Gross Activity Determination 3 times per 7' days with a 1, 2, 3 and 4 inaximum time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> '

i between samples.

2.

Isotopic Analysis for DOSE EQUIVA-1 per 14 days 1

l-LENT I-131 Concentration' i

3.

Radiochemical for E Determination 1 per 6 months 1

4.

Isotopic Analysis 'for-Iodine a) Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, if,-27, 37, 47, and 5!

2 Including I-131, 1-133, and I-135 whenever the specific m

activity exceeds 1.0 l

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pC1/ gram DOSE

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EQUIVALENT I-131 or 100/E pCi/ gram and

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I b) One sample between 1, 2, 3 and 4 l-a TilERHAL P0tlER 2 & 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following change exceeding 15 percent of the RATED TilERMAL POUER within a one hour period.

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suntil the specific activity of the primary coolant system is restore

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uithin its 1icits.

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LCA 192-Attachment B Page 14 of 23 l

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CO:W,1f t:1TffTSYSTgts,

. 00"*.*,1 ::4T! T 5TI:t'CTURAL 1 :TTGR1TY 1. Ll!'ITil:G C0t:DITIO::S FOR_ OPEP.ATI0ff

.3.6.1.6 The structural intcgrity of the containment shall be maintained

.at a level consistent with the exoptance criteria in Specification 4.6.1.6.

- ltri'LICADILITY: H0 DES 1, 2; 3 and 4.

g ACT10'!:

With the structural integrity of the containment not confonaing to the above requirements, restore the structural integrity to within the limits prior to increasing the Reactor Coolant System temperature above 200*F.

a

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-SURVEILLA! ICE REQUIREMENTS t

'4.6.1.6.1-Containment Tendonn. The containment tendons' structural integrity shall be cemenstrated at the end of one, three and five years

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'J following the initial contain:..cnt structural integrity test and at five

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year intervals thercafter. The tendons' structural integrity shall be demonstrated by:

1

. %..ining that a representative sample of at least 16 tendons (6 vet tical, and 10 hoop) cach have a lift off force of between

.[

113p (minimum) and 1545K (mar,imum) pounds.

If the lift off fofcc of any one tendon in the total srsple population is out L

of the. predicted bounds (loss than miniuum or greater than

'j maximum), an'adje. cent tendon on ecch side of the defective I

tendon shall also be checked for lift off forec. If both of these tendons are found acceptable, the surveillance-program i

may proceed considering the singic deficiency as unique and acceptable. liore than one dcfective tendon out of the original

)

sampic population is evidence of abnonci degradation of the L

containnmt structure. Unicss there is evidence of abnon al degradation of the contairent structure during the first j

j three tests of the tendons, the number of tendons checked for i

lift off force during subscquent tests toy be reduced to a h.

. l' representative sampic of at 1 cast 6 tendons (3 vertical and 3 hoop).

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l Tra?!:-U!:IT 1 3/1 6-8

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LCA 1921 Attachment B Page 15 of.23-CONTAINMENT SYSTEMS-QLCJRIC HYDROGEN RECOMBINERS' W

, LIMITING CONDITION FOR OPEP.ATION

'3.6.4.2 Two independent containment hydrogen recombiner systems shall be OPERABLE.

' APPLICABILITY: MODES-1 and 2.

ACTION:

With one hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status within-30 days or be in at least HOT STANDBY within_the~next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLAN'CE REQUIREMENTS 1-4.6.4.2. Each hydrogen recombiner system shall be demonstrated OPERABLE:

i.c.

At least once per 6 months by verifying during a recombiner a.

system functional test that :the minimum heater sheath temperature increases to 700'F within 90 minutes and is maintained for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

.b.

At least once per 1B months by:

l

?.

1.

Performing a CHANNEL CALIBRATION of-all recombiner instru-mentation and control circuits.

L' 2.

Verifying through a visual examination that there is no L

evidence of abnormal conditions within the recombiners (i.e;, loose wiring or structural connections, deposits of foreign materials, etc.)

I I

L' 3.

Verifying during a recombiner system functional tests that the heater sheath temperature increases oto E1200*F within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and is maintained for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.-

i 2

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l:

TROJAN-UNIT 1 3/4 6-26 l

1 l

l :~

V

LCA 192-Attachment B s:

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Page 16~of 23

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CONTAINMENT SYSTEMS HYOROGEN VENT SYSTEM LIMITING CONDITION FOR OPERAT*CN 3.6.4.3 At least one c:ntainment hydrogen vent system shall be OPERABLE and capable of being powered from an OPERA 8LE emergency bus.

Apot.t CAB ILITY : -MODES 1 and 2.

]-

AC~i CN':

With no containment hydrogen vent system OPERABLE, restore at least one hydrogen vent system to OPERABLE status within 30 days or be in HOT STAN08Y within 12' hours.

SURVEILLANCE REOUIREMENTS 4.6. A.3 'The above required hydrogen vent system shall be demonstrated OPERABLE:

a.

A: least once per 31 days by initia:ing flew througn the HE?A filter and charecal adscrber train and verifying tnat ne vent system operates ' for a: least.15 minutes.

O b.

At least once per 15 m nths or (1) after any stru:tural

,k maintenance on :ne HE?A filter or char: cal-adscreer housings, or (2) following painting, fire er enecical release in any ventilation zone comunicating witn the system by:

1.

herifying that the charcoal at:orters remove > 99% of a halogenated hydrocarton refrigerant test gas wnen they are tested in-place in accordance with ANSI H510-1975 while operating the vent system at a flow rate of 140 cfm

+ 10%.-

of 2.

Verifying that the HEPA filter banks remove > 99 the 00P when they are tested in-place in ac:ordan:e wi:3 ANSI N510-1975 while operating the vent system at a flow ra*e of 140 cfm 10t.

3.

Verifying within 31 days after removal that r labornt:ry 6

analysis of a caroon s=aple fr:m at least one tas cansisterM demonstrates a removal efficiency of 1 90 for radioactive methyl iodide wnen the sample is tested in ac:crdance with ANSI M510-1975 (130*C, 95: R.H.).

TROJAN-UNIT 1 3/ A 6-23 Amendment No.19 February 27, 1978

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j LCA 192.

s Attachment B l

Page 17 of 23-I l

i 00NTAINMENT SYST!*$

l l

$URVEf t, LANCE REQUIREwtNTS (Centinuedi b,

4 Verifying a system flow rata of 140 cfm + 10% during systes operation wnen tested in ac cedance with ANSI i

N510-1975.

c.

After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of chartcal adsorter coeration by i

verifying within 31 days after removal tnat a laboratory analysis of a carbon sample obtained from a test canister demonstrates a removal efficiency of n 905 of radioactive

~

methyl iodide when tne samnle is tested in ac:crdance with AN$1 N510-1975 (130'C. 95: R.H.).

d.-

At least once per 18 months by verifying that the pressues i

drop across the contined'HEPA fil ers and chre ::1 adsceter

' hanks is < 10 inenes Watar Gauge while o9ers-ing the vent system at a flow rate of 140 cfm f, lot.

4g ra.

After each complete or pa-tial replacement of a HEPA filter 4-(--

bank by verifying that the' HEPA filters reeve > 995 of tne OCP when they are tes'4ed in-clace in ac:sedance with ANSI N510-1975 while operating the vent system at a flow rate of L

14C cfm ;,10%.

f.

After each cor.rcTete er partial reciacament of a cha-c:a1 I

acscrter sank my verifying, hat tne enarc:41 tesarters re ve

> Sh of a halogenates nycrocar:en refriaerant test -

Tney are tested in-place in ac:criance wIth AN!! 197!as unen wnile operating the vent systen at a flow rate of 140 cfm + 10%.

+

/J610

,_ m ( Fin siiy~27eAmen TRCJAN-Un!T 1 3/a 5-29

- h 197

.. - ~

LCA 192

.=

Attachment B Page 18 of:23 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) at lower pressures'in H0 DES 2 or 3 by verifying that the steam turbine-driven pump starts and develops a disc arge pressure of 21470 psig on recirculation flow (when teste ) pursuant to Specification 4.0.5) when the secondary steam ressure is > 275 psig; however OPERABILITY AT 4560 RPM shall be within 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />s-af ter secondary steam pressure is increased above 800 psig.

d.

At least once per 18 months, during shutdown, by:

1.

Verifying that each automatic valve in the flow path actuates l

to its correct position or,a safety injection test signal.

[

2.

Verifying that each pump starts automatically upon receipt of each auxiliary feedwater actuation test signal in Table 4.3-2.-

By verifying that each power operated (excluding automatic) valve I

e.

in the flow path is OPERABLE when tested pursuant to Specification 4.0.5.

4.7.1.2.2 The auxiliary feedwater pump diesel shall be demonstrated OPERABLE:

a.

At least once per 31 days by:

1.

Verifying the fuel level in-its day tink, and 2.

Verifying that a sample of diesel fuel from its fuel tank is i

within the acceptable limits specified in Table 1 of ASTM I

D975-78 when checked for viscosity, water and sediment.

I b.

At least once per 18 months during shutdown by:

.l 1

1.

Subjecting the diesel to an inspection in accordance with

~

i procedures prepared in conjunction with its manufacturer's.

recommendations for this class of standby service, and

.l 2.

Verifying the diesel and pump operate for 1 60 minutes.

l 4. 7.1. 2. 3 The electric auxiliary feedwater pump shall be demonstrated l

OPERABLE-by verifying that the pump starts and develops a discharge pressure of t'1580 psig on recirculation flow within the previous 92 days of entering 1

Action Item b. of 3.7.1.2.

i i

TROJAN-UNIT 1 3/4 7-6 AmeDdDLent No. 79,58,74,//

U5,1M4]

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LCA 192

.j Attachment B Page 19 of 23 l

PtANT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued)

(

Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2 March 1g78, demonstrates a penetration of 51.0 percent when hs tested in accordance with ASTM D3803-79 Methyl Iodide Penetra-tion Test Methods at 30'C and 70 percent relative humidity.

e.

At least once per 18 months by:

1.

Verifying that the pressure drop across the combined NCPA filters and charcoal adsorber banks is < 6 inches b-Water Gauge while operating the ventilation system at a flow rate of 3000 cfm i 105.

2.

Verifying that on a safety Injection signal, the control room normal air conditioning system (CB-2) stops and isolation dampers close to automatically isolate the control room within 3 seconds; the CB-3 (Water sampling laboratory exhaust), CB-4

\\'

(toilet and lunch room exhaust), CB-5 (Control Building supply),i CB-6 (mechanical room exhaust), and CB-10 (Control Building air conditioning supply) systems stop; and that CB-1 (control room i

i omergency ventilation system) automatically starts.

3.

Verifying that on a High Radiation signal, the control room I 52 normal air conditioning system (CB-2) stops and isolation dampers close to automatically isolate the control room

'(

within 3 seconds; and the CB-3 (water sampling laboratory exhaust), CB-4 (tcilet and lunch room exhaust), CB-5 (Control Building supply), CB-6 (mechanical room exhaust), and CB-10 l

(Control Building air conditioning supply) systems stop.

4 Vertfying that on a High Chlorine signal and (Hgh 502 signal l

the control room normal air conditioning system (CB-2) stops l

and isolation dampers close to automatically isolate the con-trol room within 3 seconds; and the CB-3 (water sampling i

laboratory exhaust), CB-4 (teilet and lunch room exhaust),

CD-5 (Control Building supply), CB-5 (mechanical room exhaust), and CB-10 (Control Building air conditioning supply) systems stop.

f.

After each complete or partial replacement of HEPA filter banks by verifying that the HEPA filter unks remove 199.35fD4he 00P when they are tested in-place in eccordance with p51 N510-1975 d y:

3 while operating the filter train at a flow rate o 30001105.h IcM U

g.

After each complete.or partial replacement of a cdarcoal adsorbdr

(

bank by verifying that the charcoal adsorbers remokt 99.95%,of a f

I halogenated hydrocarbon ref rigerant test gas when they-are-tested l-

\\

in-place in accordance with ANSI N510-1975 while operating the i,l f

filter train at a flow rate of 3000 cfm 10%.

Amendmen LMo. 79 I

/

DD, 705. /'nt TROJAN-UNIT 1 3/4 7-20

LCA 192 Attachm:nt B Pcge 20 of 23

]

l REFUELING OPERATIONS DECAY TIME LIMITING CONDIT10W FOR OPERATION 3.9.3 The reactor shall be suberitical for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.

APPLICABILITY: During movement of irradiated fuel in the reactor pressure vessel.

ACTION:

With the reactor subcritical for less than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, suspend all opera-tions involving movement of irradiated feel in the reactor pressure ves sel. The provisions of Specification 3.0.3 are not applicable.

\\

SURVEILLANCE REOUIREMENTS l

4.9.3 The reacter shall be determined to have been suberitical for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> by verification of the date and time of suberiticality prior to movement rradiated fuel in the reactor pressure vessel.

te i

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TROJ AN-UNIT 1 3/4 9-3 1

LCA 192 Att acic nt B Pago 21 of 23 i

t f

trit'rt 1::G nPrrAT10t15_

f r'e'"'r:i r. AT10*:S 11l'1 Tit:*. C0 01710!; FOR OPrRAT10:1 3.9.5 Direct conn:unications shall be maintained between the control rooin I

anti perconnci at the refueling station.

Af'PL10 31L]TY: During CORE ALTERATIONS.

/.C T!'):J:

L' hen direct cc:T::unications between the control ronin and pr.rsonnel ct the retuoling ste.tien cannot b2 ticintcined, surp:nd all CORC liLTCi 'iTt0':5.

The

rcvisions of 5;;ecification 3.C.3 are not applicobic, i

(

F:7.'!CILU' CE CT U1nCI'E ;T5 4.9.5 Direct ec=.unicatiens between the control roo:n and personnel at th: refuelinJ station sh:111 be de enstrated within one hour prior to the start of cnd at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during C01:E ALTC.'.*iT10NS.

)

'Jr:.i'::1 1

3/4 9 5

LCA 192 Attachment B

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Page 22 of 23 l

1 RADIDACTIVE EFFLUENTS Pp Wyer CRS t, i

. GASEOUS RADWASTE TREATEWT

'A LIMITING CONDITION FOR OPERATION

,[

3.11.2.4 (1) Thhaseous radweste treatment system shall be maintained and used to reduce 'redfo4ctfVe~ materials ~in'gaseoss waste prior to their discharge when the gaseous effluent air doses due to gaseous effluent i

releases to unrestricted areas (see Figure 5.1-1) when averaged over a 1

calendar quarter wovid exceed 2.5 mead _fot. gamma radiation and 5.0jradw for bete radiation. (2) The(ventilation exhaust treatment systenbshell be maintained and used to redu'ef7aticactive materials ~fn'gese~ous waste i

prior to their discharge when the doses due to iodine-131, tritium and radionuclides in particulate fom with half lives greater than 8 days in gaseous effluent releases to unrestricted areas (see Figure 5.1-1) when averaged over a calendar quarter would exceed 1.25 arem to any organ.

APPLICABILITY: At all times.

_ ACTION:

a.

With gaseous waste being discharged for more than 31 days f

7 without treatment and in excess of the above limits, discuss in the Semiannual Radioactive Effluent Relea$e Report the f

following infomation:

1.

Identification of equipment not OPERABLE and the reason for inoperability.

Action (s) takeqto restore the inoperable equipment to 2.

W RABL g g pg m (ogy7 eng L 3.

Summary description of action (s) taken to prevent a f

recurrence.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVE!LLANCE REQUIREENTS 4.11.2.4.1 The average release rate of noble gases from the site _during any calendar quarter shall be such that 100 QTv Nv < 1 or 50 QTv My < l.

t f

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TROJAN. UNIT 1 3/4 11-13 A

sL mendmentJo.o me~ m i

LCA 192 Attachment B j

Page 23 of 23 pd m lower RADICACTIVE EFFLUENTS 015q

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TOTAL DOSE LIMITING CONDITION FOR OPERATION

/

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3,11.LS. bnnual (calendar year) dose or dose comitment to anyh%ER Ob

[...THE PUBLI@ue to releases of radioactivity and to radiation from urantum Tuel tycie sources shall be limited to less than or equal to 25 mrems to the

~

total body or any organ, except the thyroid, which shall be limited to less then or equal to 75 mrems.

APPLICABILITY: At all times, e};

ACTION:

4 a.

With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specification 3.11.1.2, 3.11.2.2, or 3.11.2.3, A

calculations should be made including direct radiation contri-

/99\\

butions from the reactor unit and from outside storage tanks to determine whether the above limits of Specification F,.11.2.5 have been exceeded and prepare and submit to the Comission within 30 days a Special Report pursuant to 10 CFR 20.405(c)(1)andSpecification6.9.2.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not l

applicable, l

SURVE!LLANCE REQUIREMENTS f

4.11.2.5.1 Cumulative dese contributions from liquid and gaseous effluents L

shall be determined in.accordance with Specifications 4.11.1.2, 4.11.2.2, t

and 4.11.2.3, and in accordance with the methodology and parameters in the ODCM.

l 4.11.2.5.2 Cumulative dose contributions from direct radiation from the reactor unit and from outside storage tanks shall be determined in accordancel with the methodology and parameters in the ODCM. This requirement is appli-i cable only under conditions set forth in Specification 3.11.2.5.a.

(

\\ 'd TROJAN-UNIT 1 3/4 11-is j

N o..

4

.